Assessment of reactor vessel integrity (ARVI)

Nuclear Engineering and Design

Volumn 221, Issue 1-3 SPEC., 2003, Pages 23-53

  Sehgal, B R ^a   Theerthan, A ^a   Giri, A ^a   Karbojian, A ^a   Willschutz H G ^b   Kymalainen O ^c   Vandroux, S ^d   Bonnet, J M ^d   Seiler, J M ^d   Ikkonen, K ^e   Sairanen, R ^e   Bhandari, S ^f   Burger M ^g   Buck, M ^g   Widmann, W ^g   Dienstbier, J ^h   Techy, Z ⁱ   Kostka, P ⁱ   Taubner, R ⁱ   Theofanous, T ^j   Dinh, T N ^j   more..

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

^b INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

^c Fortum Oil and Gas Oy   (Finland)

^d CEA GRENOBLE   (France)

^e VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

^f AREVA NP   (France)

^g UNIVERSITY OF STUTTGART   (Germany)

^h NUCLEAR RESEARCH INSTITUTE   (Czech Republic)

ⁱ VEIKI Institute for Electric Power Research   (Hungary)

^j UNIVERSITY OF CALIFORNIA   (United States)

more..

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTATIONAL FLUID DYNAMICS; COOLING; HEAT FLUX; PRESSURE VESSELS;

REACTOR VESSEL;

NUCLEAR REACTORS;

EID: 0037375397     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00343-6     Document Type: Conference Paper

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